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NEA-1715 IRPHE-JAPAN.

IRPHE-JAPAN, Reactor Physics Experiments carried out in Japan

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1. NAME OR DESIGNATION OF PROGRAM:  IRPHE-JAPAN.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
IRPHE-JAPAN NEA-1715/02 Arrived 18-FEB-2004

Machines used:

Package ID Orig. computer Test computer
NEA-1715/02 Many Computers
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3. DESCRIPTION

A vast program of reactor physics experiments was carried out in Japan. It covers the areas of:
- thermal reactors
- advanced thermal reactors
- high temperature reactors
- very high temperature reactors
- triga reactors
- fast reactor
- various other experimental facilities
  
A number of primary documents produced at the end of the experimental campaign has been made available to the International Reactor Physics Benchmark Experiments Project (IRPhE).
These documents are collected here and are characterised as follows:
- TCA Experiments
- DCA Experiments - Research on ATR
- Research on Criticality Safety
- Fast Reactor Experiments
- Very High Temperature Reactor Critical (VHTRC) Assembly
- Triga Experiments (Musashi)
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9. STATUS
Package ID Status date Status
NEA-1715/02 18-FEB-2004 Masterfiled restricted
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10. REFERENCES

DOCUMENTS AVAILABLE:
  
A. TCA Experiments
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(1) "Precise Determination of beff for Water-Moderated U And U-Pu Cores by a Method Using Buckling Coefficient of Reactivity", (including Supplement - Fuel rod specification), Takenori Suzaki, Kiyoshi Sakurai, Ken Nakajima, and Ohichiro Horiki (Japan Atomic Energy Research Institute) TCA-PU-16, and Proc. ICNC'99 Versailles, France, p. 386 (1999)
  
(2) "Critical Experiments on Light-Water Moderated PuO2-UO2 Lattices", Iwao Kobayashi, Harumichi Tsuruta, Takenori Suzaki, Akio Ohno, Kiyonobu Murakami, and Shojiro Matsuura (Japan Atomic Energy Research Institute), Ryozo Yumoto, Tadakuni Matsumoto, Hideyoshi Sasajima, and Kazuo Itagawa (Power Reactor and Nuclear Fuel Development Corporation), Journal of Nuclear Science and Technology 15(3), pp. 166-182 (March 1978). TCA-PU-9
  
(3) "Critical Sizes of Light-Water Moderated UO2 and PuO2-UO2 Lattices", Haruchumi Tsuruta, Iwao Kobayashi, Takenori Suzuki, Akio Ohno, Kiyonobu Murakami, and Syojiro Matsuura (Japan Atomic Energy Research Institute), JAERI 1254 (February 1978), TCA-PU-10
  
(4) "Measurement of Reactivity Worths of Sm, Cs, Gd, Nd, Rh, Eu, B and Er Aqueous Solution Samples", Yuichi Komuro, Takenori Suzaki, Shoichi Ohtomo, Kiyoshi Sakurai, and Oichiro Horiki (Japan Atomic Energy Research Institute) JAERI-Research 97-088 (november 1997)
  
(5) "Temperature Effects on Reactivity in Light Water Moderated UO2 Cores with Soluble Poisons", Yoshinori Miyoshi, Toshihiro Yamamoto, Takenori Suzaki, and Iwao Kobayashi (Department of Fuel Safety Research, Japan Atomic Energy Research Institute), Journal of Nuclear Science and Technology, 29(12), pp. 1201-1211 (December 1992). Technical Report
  
(6) "Analytical Study of Two-Region TCA Critical Experiments with PWR-Type MOX Fuel by Using Monte Carlo Code MVP", Mafizur Rahman, Takenori Suzaki, and Takamasa Mori (Japan Atomic Energy Research Institute), JAERI-Research 2003-007 (March2003)
  
(7) "Effects of Volume Fraction and Non-uniform Arrangement of Water Moderator on Reactivity" X. Cao, T. Suzaki, T. Kugo, T. Mori (Japan Atomic Energy Research Institute), JAERI-Tech 2003-069 (August 2003)
(included in February 2004)
  
DCA experiments
B. Research on ATR
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(1) Substitution Measurements on 28-Fuel-Rod Critical Clusters in D20 and Their Analysis by the Second-Order Perturbation Method, K. Shiba, Nucl. Sci. Eng., 65, 492-507 (1978)
  
(2) Lattice Parameter Measurements on Cluster-Type Fuel for Advanced Thermal Reactor, Y. Hachiya, N. Fukumura, A. Nishi, K. Iijima, and H. Sakata, J. Nucl. Sci. Techn., 13(11), 618-632 (1976)
  
(3) Measurement of Local Power Peaking Factors in Heavy-Water Moderated Plutonium Lattices, N. Fukumura, J. Nucl. Sci. Techn., 18(4), pp.285-299 (1981)
  
(4) Analysis of Heavy-Water-Moderated, Cluster-Type Fuel Lattices by Cluster Physics Code 'MESSIAH', H. Kadotani, and Y. Hachiya, J. Nucl. Sci. Techn., 19(9), pp.689-704 (1982)
  
(5) Fuel Temperature Coefficients of Reactivity for Heavy-Water-Moderated, Cluster-Type Fuel Lattices, H. Sakata, Y. Hachiya, and H. Kadotani, J. Nucl. Sci. Techn., 17(10), pp.747-763 (1980)
  
(6) Measurements of Moderator Temperature Coefficients of Reactivity for Pressure-Tube-Type Reactors, T. Otsuka, N. Fukumura, and Y. Hachiya, Nucl. Sci. Eng., 74, 95-105 (1980)
  
(7) Thermal-Neutron Behavior in Cluster-Type Plutonium Fuel Lattices, T. Wakabayashi, and Y. Hachiya, Nucl. Sci. Eng., 63, 292-305 (1977)
  
(8) Critical Experiments on Gadolinium Poisoned Cluster-Type Fuel Assemblies in Heavy Water Lattices, T. Wakabayashi, and I. Minatsuki, Nucl. Sci. Eng., 83, 50-62 (1983)
  
(9) Study on Coolant Void Reactivity of Pressure-Tube-Type Heavy Water Lattice by the Substitution Method, Y. Kowata, and N. Fukumura, Nucl. Sci. Eng., 99, 299-312 (1988)
  
(10) Axial Dependence of Partial Void Reactivity in a Light-Water-Cooled, Heavy WaterModerated, Pressure-Tube Reactor, N. Aihara, N. Fukumura, H. Kadotani, and Y. Hachiya, Nucl. Sci. Eng., 109, 158-170 (1991)
  
(11) Neutron Absorber Effect on Coolant Void Reactivity in a Pressure-Tube-Type Heavy Water Reactor, Y. Kowata, and N. Fukumura, Nucl. Sci. Eng., 108, 308-318 (1991)
  
(12) Influence of Burnable Gadolinia Poison on Coolant Void Reactivity in a Pressure-Tube-Type Heavy Water Reactor, Y. Kowata, and N. Fukumura, Nucl. Sci. Eng., 115, 205-218 (1993)
  
(13) Reactivity Worths of Annular Control Rods in a Pressure-Tube-Type Heavy Water Lattice, M. Ueda, M. Matsumoto, and T. Haga, Nucl. Sci. Eng., 62, 559-570 (1977)
  
(14) Effect of a 0.3-eV Resonance Cross Section for Plutonium on the Coolant Void Reactivity in a Heavy Water Lattice, Y. Kowata, and N. Fukumura, Nucl. Sci. Eng., 127, 89-103 (1997)
  
  
C. Research on Criticality Safety
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(1) Subcriticality Monitoring by Feynman-alpha Method, N.Ohtani, and T.Hazama, The Fifth International Conference on Nuclear Criticality Safety, Albuquerque, New Mexico, U.S.A. Sep. 17-21, 1995, Volume II 11.43 (1995).
  
(2) Improved 252Cf-Source-Driven Noise Analysis Method Based on Time Domain Analysis, T.Hazama, The Sixth International Conference on Nuclear Criticality Safety, Versailles, France, Sep. 20-24, 1999, Volume III, 1243-1251 (1999)
  
(3) Reduction of Delayed-Neutron Contribution to Variance-to-Mean Ratio by Application of Difference Filter Technique, K. Hashimoto, T. Mouri, and N. Ohtani, J. Nucl. Sci. Techn., Vol.36, No.7, pp.555-559 (1999)
  
  
D. Fast Reactor Experiments from (JNC)
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(1) Integral Test of JENDL-3.2 Data by Re-analysis of Sample Reactivity Measurements at Fast Critical Facilities, JNC TN9400 2001-043 (February, 2001) O-arai Engineering Center Japan Nuclear Cycle Development Institute
  
  
E. Very High Temperature Reactor Critical (VHTRC) Assembly
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1."VHTRC Temperature Coefficient Benchmark Problem"
Hideshi Yasuda, Tsuyoshi Yamane, and Toshinobu Sasa (Department of Reactor Engineering, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken), JAERI-Data/Code 94-013, (October 1994)
   
  
F. Musashi Triga Experiments
----------------------------
  
(1) Benchmark Analysis of Criticality Experiments in the TRIGA Mark II Using a Continuous Energy Monte Carlo Code MCNP, T. Matsumoto, J. Nucl. Sci. and Techn. Vol 35, No. 9, pp. 662-670 (September 1998)
  
(2) A Proposal to Asian Countries with Operating Research Reactors for Making Nuclear Criticality Safety Benchmark Evaluations, Y. Komuro, J. Nucl. Sci & Techn. Vol 37, No. 6, pp. 548-554 (June 2000)
  
(3) Benchmark Analysis of TRIGA Mark II Reactivity Experiment Using a Continuous Energy Monte Carlo Code MCNP, T. Matsumoto, and N. Hayakawa, J. Nucl. Sci. and Techn. Vol 37, No. 12, pp. 1082-1087 (December 2000)
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11. HARDWARE REQUIREMENTS:  Requires HTML browser and Acrobat Reader.
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
JAERI
Tokai Mura, Naka-gun
Ibaraki-ken 319-1195
Japan
  
Japan Nuclear Cycle (JNC) Developement Institute
Tokai-mura, Naka-gun
Ibaraki, 319-1184
Japan
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16. MATERIAL AVAILABLE
NEA-1715/02
Primary documents submitted by Japan for the IRPhE Project
(see item 10)
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: benchmarks, criticality, experiment, fast reactors, thermal reactors.